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Numerical simulation of an explosion in a simple scale model of a nuclear reactor

Wybrane pełne teksty z tego czasopisma
Identyfikatory
Warianty tytułu
Konferencja
8th International Conference on Numerical Methods in Continuum Mechanics (September 19-24, 2000 ; Liptovsky Ján, Low Tatras ; Slovakia)
Języki publikacji
EN
Abstrakty
EN
In the case of a Hypothetical Core Disruptive Accident (HCDA) in a Liquid Metal Fast Breeder Reactor, it is assumed that the core of the nuclear reactor has melted partially and that the chemical interaction between molten fuel and liquid sodium creates a high pressure gas bubble in the core. The violent expansion of this bubble loads and deforms the reactor vessel, thus endangering the safety of the nuclear plant. The experimental test MARA 8 simulates the explosive phenomenon in a mock-up enclosed in a flexible vessel with a flexible roof. This paper presents a numerical simulation of the test and a comparison of the computed results with the experimental results and previous numerical ones.
Rocznik
Strony
489--517
Opis fizyczny
Bibliogr. 40 poz., rys., tab., wykr.
Twórcy
autor
  • CEA Saclay, SEMT-DYN, 91191 Gif sur Yvette cedex, France
autor
  • CEA Saclay, SEMT-DYN, 91191 Gif sur Yvette cedex, France
autor
  • Socotec Industrie, 1 av. du Parc, 78180 Montigny le Bretonneux, France
autor
  • Novatome, NVPM, 10 rue Juliette Récamier, 69006 Lyon, France
Bibliografia
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  • [3] A. Benuzzi. Comparison of different LMFBR primary containment codes applied to a benchmark problem. Nuclear Engineering and Design, 100: 239-249, 1987.
  • [4] Y. Blanchet, P. Obry, J. Louvet. Treatment of fluid-structure interaction with the SIRIUS computer code. In: J. Rastoin, ed., Proc. 6th mt. Conf. on Structural Mechanics In Reactor Technology, paper B8/8. Int. Association for Structural Mechanics in Reactor Technology and Commission of the European Communities, Luxembourg, 1981.
  • [5] C. Bour, M. Sp6randio, J. Louvet, C. Rieg. LMFBR's core disruptive accident. Mechanical study of the reactor block. In: A.H. Hadjian, ed., Proc. 10th mt. Conf. on Structural Mechanics In Reactor Technology, Vol. E, 281-287. American Association for Structural Mechanics in Reactor Technology, Los Angeles, USA, 1989.
  • [6] Y. Cariou, M. Sp6randio, M. Lepareux, K. Christodoulou. LMFBR's whole core accident. Validation of the PLEXUS code by comparison with MARA tests. In: K.F. Kussmaul, ed., Proc. 12th mt. Conf. on Structural Mechanics In Reactor Technology, Vol. E, 209-214. Int. Association for Structural Mechanics in Reactor Technology, Amsterdam, Netherlands, 1993.
  • [7] Y. Cariou, J.P. Pirus, C. Avallet. LMR large accident analysis method. In: M. Livolant, ed., Proc. 14th mt. Conf. on Structural Mechanics In Reactor Technology, Vol. P, 395-402. Int. Association for Structural Mechanics in Reactor Technology and Commissariat l'Energie Atomique, Paris, France, 1997.
  • [8] F. Casadei, A. Daneri, G. Toselli. Use of PLEXUS as a LMFBR primary containment code for the CONT benchmark problem. In: A.H. Hadjian, ed., Proc. 10th ml. Conf. on Structural Mechanics In Reactor Technology, Vol. E, 299-304. American Association for Structural Mechanics in Reactor Technology, Los Angeles, USA, 1989.
  • [9] C. Chavant, A. Hoffmann, P. Verpeaux, J. Dubois. Plexus: A general computer code for explicit Lagrangian computation. In: T.A. Jaeger, ed., Proc. 5th ml. Conf. on Structural Integrity In Reactor Technology, paper B2/8. Int. Association for Structural Mechanics in Reactor Technology and Commission of the European Communities, Luxembourg, 1979.
  • [10] A. Daneri et al. Influence of the representation models of the stress-strain law on the LMFBR structures in an HCDA. In: J. Rastoin, ed., Proc. 6th mt. Conf. on Structural Integrity In Reactor Technology, paper E4/4. Int. Association for Structural Mechanics in Reactor Technology and Commission of the European Communities, Luxembourg, 1981.
  • [11] F. David. Etude d'une composition explosive flegmatis6e. Applications a, la &formation d'une cuve. In: Proc. Symposium sur las hautes pressions dynamiques. Paris, France, 1978.
  • [12] C. Fiche, J. Louvet, B.L. Smith, A. Zucchini. Theoretical experimental study of flexible roof effects in an HCDA's simulation. In: J. Stalpaert, ed., Proc. 8th mt. Conf. on Structural Integrity In Reactor Technology, Vol. E, 139-144. Commission of the European Communities and Int. Association for Structural Mechanics in Reactor Technology, Luxembourg, 1985.
  • [13] A. Hoffmann, M. Lepareux, B. Schwab, H. Bung. Plexus - A general computer program for fast dynamic analysis. In: Proc. Conf. on Structural Analysis and Design on Nuclear Power Plant. Porto Alegre, Brazil, 1984.
  • [14] H. Holtbecker. Testing philosophy and simulation techniques. Nuclear Engineering and Design, 42: 75-87, 1977.
  • [15] N.E. Hoskin, M.J. Lancefield. The COVA programme for the validation of computer codes for fast reactor containment studies. Nuclear Engineering and Design, 46: 17-46. 1978.
  • [16] K.C. Kendall, A. Benuzzi. The COVA programme: Validation of the fast reactor containment code SEURBNUK. Nuclear Engineering and Design, 57: 79-105, 1980.
  • [17] K.C. Kendall, D.J. Adnams. Experiments to validate structural dynamics code used in fast reactor safety assessment. Science and Technology of Fast Reactor Safety, Vol. 2. British Nuclear Energy Society, London, England, 1986.
  • [18] M. Lepareux, B. Schwab, A. Hoffmann, P. Jamet, H. Bung. Un programme g6n6ral pour l'analyse dynamique rapide - Cas des tuyauteries. In: Proc. Colloque Tendances Actuelles en Calcul des Structures. Bastia, France, 1985.
  • [19] M. Lepareux, B. Schwab, H. Bung. Plexus: A general computer program for the fast dynamic analysis - The case of pipe circuits. In: J. Stalpaert, ed., Proc. 8th mt. Conf. on Structural Mechanics In Reactor Integrity, Vol. Fl, 39-46. Commission of the European Communities and Int. Association for Structural Mechanics in Reactor Technology, Luxembourg, 1985.
  • [20] M. Lepareux, H. Bung, A. Combescure, J. Aguilar. Analysis of a CDA in a LMFBR with a multiphasic and multicomponent behaviour law. In: H. Shibata, ed., Proc. 11th mt. Conf. on Structural Mechanics In Reactor Integrity, Vol. E, 371-376. Atomic Energy Society of Japan and Int. Association for Structural Mechanics in Reactor Technology, Tokyo, Japan, 1991.
  • [21] M. Lepareux, H. Bung, A. Combescure, J. Aguilar, J.F. Flobert. Analysis of an HCDA in a fast reactor with a multiphase and multicomponent behavior law. In: K. Kussmaul, ed., Proc. 12th mt. Conf. on Structural Mechanics In Reactor Integrity, Vol. E, 197-202. Int. Association for Structural Mechanics in Reactor Technology, Amsterdam, Netherlands, 1993.
  • [22] M. Lepareux, J.M. Michelin, D. Thiault. Plexus-R: une extension de Plexus la robotique. CEA report DMT/94-138, 1994.
  • [23] J. Louvet, P. Hamon, B.L. Smith, A. Zucchini. MARA 10: an integral model experiment in support of LMFBR containment analysis. In: F.H. Wittmann, ed., Proc. 9th mt. Conf. on Structural Mechanics In Reactor Integrity, Vol. E, 331-337. A.A. Balkema, Rotterdam, Netherlands, 1987.
  • [24] J. Louvet. Containment response to a core energy release. Main experimental and theorical issues - Future trends. In: A.H. Hadjian, Proc. 10th hat. Conf. on Structural Mechanics In Reactor Integrity, Vol. E, 305-310. American Association for Structural Mechanics in Reactor Technology, Los Angeles, USA, 1989.
  • [25] M.F. Robbe, M. Lepareux, H. Bung. Plexus - Notice thgorique. CEA report DMT/94-490, 1994.
  • [26] M.F. Robbe, M. Lepareux, N. Vivien, G. C6nOrino. Screening calculations on the vessel lower head behaviour due to an in-vessel steam explosion. In: M. Livolant, ed., Proc. 14th mt. Conf. on Structural Mechanics In Reactor Technology, Vol. P, 451-458. Int. Association for Structural Mechanics in Reactor Technology and Commissariat l'Energie Atomique, Paris, France, 1997.
  • [27] M.F. Robbe, P. Galon, T. Yuritzinn. Castem-Plexus: Un logiciel de dynamique rapide pour ćvaluer l'int6grit6 des structures en cas d'accident. In: J. Fabri, ed., Proc. 4th Conf. INSTRUC. Société Franqaise des Mékaniciens, Courbevoie, France, 1999.
  • [28] M.F. Robbe, M. Lepareux. Scoping calculations of an in-vessel steam explosion. CASTEM-PLEXUS computations. In: Proc. 8th mt. Conf. On Nuclear Engineering, paper 8269, CD-rom. American Society of Mechanical Engineers, New York, USA, 2000.
  • [29] M.F. Robbe, M. Lepareux. Estimation of the mechanical consequences of an in-vessel steam explosion by means of parametric computations. In: V. Kompiś, ed., Proc. 8th International Conference on Numerical Methods in Continuum Mechanics, CD-rom. University of Žilina, Žilina, Slovak Republic, 2000.
  • [30] M.F. Robbe, M. Lepareux, C. Trollat. Assessment of the hydrodynamic loads due to a LOCA in a 3-loop PWR. Pipe computations with the code CASTEM-PLEXUS. In: V. Kompiś, ed., Proc. 8th mt. Conf. On Numerical Methods in Continuum Mechanics, CD-rom. University of Žilina, Žilina, Slovak Republic, 2000.
  • [31] M.F. Robbe, Y. Cariou, M. Lepareux, E. Treille. Numerical simulation of a Hypothetical Core Disruptive Accident in the MARA 8 mock-up with the CASTEM-PLEXUS computer code. In: V. Kompiś, ed., Proc. Int. Conf. on Numerical Methods in Continuum Mechanics 2000, CD-rom. University of Žilina, Žilina, Slovak Republic, 2000.
  • [32] M.F. Robbe, Y. Cariou, M. Lepareux, E. Treille. Validation of the Core Disruptive Accident constitutive law of the Castem-Plexus code on the Mara8 test. In: H. Nguyen-Dang, ed., Proc. Int. Colloquium in Mechanics of Solids, Fluids, Structures and Interactions. LTAS - Université de Liége, Liége, Belgique, 2000.
  • [33] M.F. Robbe, N. Vivien, M. Valette, E. Berglas. Use of thermalhydraulic and mechanical linked computations to estimate the mechanical consequences of a steam explosion. Journal of Mechanical Engineering, 52: 65-90, 2001.
  • [34] M.F. Robbe, M. Lepareux, E. Treille, Y. Cariou. Numerical simulation of a Core Disruptive Accident and comparison with the simple test Mara 8. In: D. Todd, ed., Proc. ANS/HPS Student Conference "2001: A nuclear odyssey", CD-rom. American Nuclear Society, USA, 2001.
  • [35] M.F. Robbe, M. Lepareux. Evaluation of the mechanical consequences of a steam explosion in a nuclear reactor. Bulgarian Journal of Theoretical and Applied Mechanics, in print, 2002.
  • [36] M.F. Robbe, M. Lepareux, C. Trollat. Hydrodynamic loads on a PWR primary circuit due to a LOCA. Nuclear Engineering and Design, 211(2-3): 189-228, 2002.
  • [37] J.E.A. Sidoli, K.C. Kendall. The WINCON programme - Validation of the fast reactor primary containment codes. In: D.G. Walton, ed., Proc. INE mt. Conf. On Nuclear Containment. Nuclear Containment Structures, Cambridge University Press, 1988.
  • [38] B.L. Smith, C. Fiche, J. Louvet, A. Zucchini. A code comparison exercise based on the LMFBR containment experiment MARA-04. In: J. Stalpaert, ed., Proc. 8th mt. Conf. on Structural Mechanics In Reactor Technology, Vol. E, 151-157. Commission of the European Communities and Int. Association for Structural Mechanics in Reactor Technology, Luxembourg, 1985.
  • [39] E. Struder, P. Galon. Hydrogen combustion loads Plexus calculations. Nuclear Engineering and Design, 174: 119-134, 1997.
  • [40] H.U. Wenger, B.L. Smith. On the origin of the discrepancies between theory and experiment in the COVA series. In: F.H. Wittmann, ed., Proc. 9th mt. Conf. on Structural Mechanics In Reactor Technology, Vol. E, 339-344.
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-article-BPB2-0006-0080
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